ML20248C684

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Rev 1 to 09334281-01, RCS Internal Voltage Decay on Loss of A01/A02 4 Kv Bus
ML20248C684
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 03/30/1998
From: Ashrafi H, Bloethe W, Mark Flynn
SARGENT & LUNDY, INC.
To:
Shared Package
ML20248C660 List:
References
09334281-01, 09334281-01-R01, 9334281-1, 9334281-1-R1, NUDOCS 9806020224
Download: ML20248C684 (50)
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{{#Wiki_filter:NPL 98-0431 Attaciunent 5' 4 Calculation Reactor Coolant Pump Internal Voltage Decay on Loss of A01/A02 4kV Bus Voltage 9 i ~ 9906020224 990528 PDR AD0cn 03000266; P PDR j'j ~ U

SARGENT & LUNDY DESIGN INFORMATION TRANSMITTAL ENGINEERS X SAFETY-RELATED NON-SAFETY RELATED DIT No. - DIT-PB-EXT-0283-01 Page 1 of 1 CLIENT Wisconsin Electric Power Comoany To E. C. Gross - WE STATION.Eoint Beach UNIT (S) 1&2 PROJECT NO(S) 09334-281 SUBJECT Reactor Coolant Pumo Internal Voltage Decay on Loss of A01/A02 4kV Bus Voltage MODIFICATION OR DESIGN CHANGE NUMBER (S) N/A 03 3i!N M. G. Fivnn PSBG PREPARER M.f Ast MNT NAMo DIVISION P PARER'S NATURE ISSUE DATE STATUS OF INFORMATION (This information is approved for use. Design information, a proved for u, that contains assumptions or is preliminary or requires further verification (review) shall be so identified.) This information is approved and requires no further verification. This information is provided in scCordance with the terms and conditions of the service agreement / contract between sargent & Lundy (s&W and its chent governing the associated services. With respect to any third party use, s&L does not assume any obhgation to said third party as to the accuracy, completeness, usefu6 ness, or non intnnging nature of such information. IDENTIFICATION OF THE SPECIFIC DESIGN INFORMATION TRANSMITTED AND PURPOSE OF ISSUE (List any supporting documents attached to DIT by its title, revision andler issue cate, and total number of pages for each supporting document.) This design transmittal includes Calculation 9334281-01, Rev.1 " Reactor Coolant Pump Internal Voltage Voltage Decay on Loss of A01/A02 4kV Bus Voltage". This calculation was prepared to determine an analytical limit voltage for the undervoltage function of the undervoltage relays associated with each RCP supply bus. In the context of this calculation, analyticallimit refers to the lowest possible RCP supply bus undervoltage operating point which will allow a maximum reactor trip time of 1.5 seconds in response to the Complete Loss of Flow design basis accident signal. The calculation was revised to incorporate maximum intentional udervoltage relay delay from DE&SC Calc PBNP-lC 33, Rev. O. The location of the purpose, methodology, assumptions and conclusions are listed on Table of Contents (page 2 of the calculation). SOURCE OF INFORMATION Calc. No. 9334281-01 Rev.1 Report No. N/A Rev, and/or date Rev. and/or dete other DISTRIBUTION File 2.40 J. D. Regan (1/1) WE File w__-__-_.__.____

ISSUE

SUMMARY

Form GES-320.10.4. Revision 3 1 DESIGN CONTROL

SUMMARY

DESIGN VERIFICATION - PAGE 1

lCUENT, Wisconsin Electric UNIT NO.:

1&2 PROJECT NAME. Point Beach PROJECT NO.: 09334-281 CALC. NO.: 09334281 01 H SAFETY-RELATED TITLE: Reactor Coolant Pump internal Voltage Decay on Loss of A01/A02 4kV Bus Voltage cA STATUS: COMMENT SERIAL EOUPMENTNO.: O NON-SAFETY-RELATED NO. NO. IDENTIFICATION OF PAGES ADDED/ REVISED /SUPERSEDEDNOIDED & REVIEW METHOD First leeue, pages 1 through 33, Attachment pages A1-A36, Bi-B4, C1-C3, Di-D4, E1-E3, F1-F2, and G1-G2. NOTE: PRINT AND SIGN IN THE SIGNATURE AREAS BELOW l REVIEW METHOD: Detailed review of the orignal ceicuistion (Both REV. 0 hand Propared and Computer Aided Design DATE FOR REV.: 07/314 7 C*W), all of coic but Appendix G. Rev6ew by on ellemate, simpitfied or opprosamete method of + m, Appender G l PREPARER h*ano Vll.A and Vill.A properation: H. Ashren DATE:0&3097 Romerung Sechone properation: R. M. Higdon REVIEWER. William G. Bioethe DATE:0&3G97 The rouiewers eVetun heicates compience uth GES 320.10 and the nnsco6on of the Mowing nuranum Mems: correctness of math Whandpropered +%, appropneteness of kput dete, appropneteness of assumphons, and appropneteness of the ce6cutehon monod l APPROVER S. Z. Hadded DATE:07/31n7 ( IDENTIFICATION OF PAGES ADDED/ REVISED /SUPERSEDEDNOIDED & REVIEW METHOD I Pages 1-28, A1 A18, F2, and G2 rewteed to incorporate maamum intenhonal undervoltage reiey trne deisy from Duke Engmeering & Services Calculation PBNP-lC 33 Rev. D. l REVIEW METHOD: A detailed twiew of the revised pages and REV.f componeon with Rev. O of the celc. DATE FOR REV.: 030098 l PREPARER Section IV.B.2.c preparation: H. As%fl /hly 030G98 Romeining Sechons procershon: R. M. Higdon ,b l REVIEWER Wimum G. Bioethe MMA ' /7/5/ A DA7)?:030Gea j 1 The renewers s6gnature bcscates comp 6ence wth GES 320.10 and the nonicanon of the Mowing mnnwm Mems: correctness of moth W handprepered Caeculeeons, appropneteness of Mput cete, appropneteness of essump6ans, and appq-u-se of top caecuteeon l APPROVER S. Z. Hedded h ^^- DATE:030098 IDENTIFICATION OF PAGES ADDED/ REVISED /SUPERSEDEDNDIDED & REVIEW METHOD l REVIEW METHOD: REV. DATE FOR REV.: l PREPARER DATE: REVIEWER DATE: The nwowers monature hdcenes compience mth GES 320.10 and the wreicehon of the Moung nwwnum Rems: correctnnse of me@ W handprepared calcuineons, appropneteness of hput date, appropneteness of eseumphons, and appropneteness of the ce6culenon method l APPROVER DATE: t GES320lS. DOC Page 1 of 1 Rev. Date: 09-16 1997 Eff. Oste: 10 20-1997 i

Calc. For React:r Coolant Pump intomal Vcitag3 Calc. Ns. 09334281-01 W"" Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date X Safety-Related l Non.Sofety-Reisted Page 2 of 28 Client Wisconsin Electric Prepared by. Date Project Point Beach Units 1 & 2 Reviewed by Date Prof. No. 09334 281 Equip. No. Approved by Date TABLE OF CONTENTS Section Contents Page No. l. ISSUE

SUMMARY

.......................................... 1 II. TABLE OF CONTENTS .......................................2 Ill. PU RPOS E/S COPE........................................... 4 IV. IN PUT D ATA ............................................. 6 V. AS S UM PTI ON S............................................ 9 VI. ACC EPTAN CE CRITERIA..................................... 10 Vll. M ETH OD OLOG Y........................................... 1 1 Vill. CALCULATIONS and RESULTS................................. 20 IX. COMPARISON of RESULTS with ACCEPTANCE CRITERIA.............. 25 i I X. CONCLUSIONS ...........................................25 XI. RECOMM EN D ATION S....................................... 2 5 ) Xll. R E F E R EN C E S............................................. 2 6 Attachments i A Miscellaneous References.................................... A1 A18 B Case 1 - RCP Pumping Cold Reactor Coolant - Confirm input Data reflects Operation at Motor Rated Voltsgo and Calculate RCP Motor y Shaft Output Po wer................................. B1 B4 ' ~ l e C Case 1 - RCP Pumping Cold Reactor Coolant - Calculate Motor internal Voltage during Operation at Maximum Expected Supply Bus Voltage..... C1-C3 D Case II-RCP Pumping Hot Reactor Coolant - Confirm input Data reflects Operation at Motor Rated Voltage and Calculate RCP Motor Shaft Output Power................................. D 1 -D4 E Case il - RCP Pumping Hot Reactor Coolant - Calculate Motor intamal Voltage during Operation at Maximum Expected Supply Bus Voltage..... E1 E3

Calc. For React:r Coolant Pump Intemal Vcitag? Calc. N2. 09334281-01 W"* Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date /D X Safety-Related Non Safety-Related Page 3 of 28 W Client Wisconsin Electric Prepared by Date Project Point Beach Units 1 & 2 Reviewed by Date Proj. No. 09334-281 Equip. No. Approved by Date TABLE OF CONTENTS (continued) F RCP Motor Internal Voltage Decay............................... F1-F2 l G RCP M otor Deceleration...................................... G1 -G2 i I \\ l I ii i i c l l

1 Calc. For React:r Coolant Pump Intemel Vcitage Calc. Ns. 09334281-01 1-- W* Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date l Non-Safety-Related Page 4 of 28 X Safety-Reisted l Client Wisconsin Electric Prepared by Date l l Project Point Beach Units 1 & 2 Reviewed by Date Prol. No. 09334-281 Equip. Nu. Approved by Date E PURPOSE / SCOPE A. Purpose The purpose of this calculation is to determme an analyticallimit voltage for the undervoltage f'. ution of the undervoltage relays associated with each RCP supply bus. In the context of this calculation, " analytical t limit" reias to the lowest possible RCP supply bus undervoltage operating point which will still allow a f maxunum reactor trip time of 1.5 seconds in response to the Complete loss of Flow (CLOF) design basis accident signal. The analytical linut voltage derived in this calculatica will be compared to the defmition ofloss of RCP supply bus voltage given in the Point Beach Nuclear Station Technical Specifications. B. Scope here are four Reactor Coolant Pumps (RCPs),2 per unit (Reference XII B and XII D). De Unit 1 RCPs are supplied fmm non-safeguards 4160 volt buses 1-A01 and 1 A02, and the Unit 2 RCPs are supplied from non-safeguards 4160 volt buses 2-A01 and 2-A02 (Reference XILB and XII.D). He RCP motors I (6000 HP) are the largest of several motors supplied from each of these buses (Reference XII.D). Voltage at each of the above 4160 volt buses is sensed by two 4200-120 volt ratio potential transformers (pts)(Referetxv XII.D). Two ABB 27D undervoltage relays are connected in the PT secondary circuits, with one relay connected between A and B phases and one relay connected between B and C phases (References XII.D, XII.E and XII.L). The output contacts of these undenoltage relays are connected such that when they are actuated, they establish a loss of bus voltage signal (References XII.L XILN, and XII.0). j 1 For either unit, a simultaneous loss of AC voltage at both 4160 volt buses which supply the RCPs is an i initiator of the Complete loss ofFlow (CLOF) design basis accident signal (References XILA and X11C). The accid:nt analysis for the CLOF assumes a maxunum reactor trip response time of 1.5 nd until { i l reactor control rods begin to drap (Reference XILA). This reactor trip response time includes the followmg { i delays in the reactor trip circuit (References XILF and XILQ): t i I

Calc. For React r Coolant Pump intemel Vcitag) Calc. Ns. 09334281-01 8 '8 Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date u-r X Sofsty-Related l Non Sofety-Related Page 5 of 28 v Client Wisconsin Electric Propered by Date Project Point Beach Units 1 & 2 Reviewed by Date ProJ. No. 09334-281 Equip. No. Approved by Date _Ill., PURPOSE / SCOPE (continued) J ltem Delav Description L-1 Transient voltage decay The time from the instant ofloss of power to the RCP buses until the time actuation of the undervoltage function of the undervoltage (loss of voltage) relay associated with the RCP supply bus. This delay aRer the postulated loss of power to the supply bus is caused by the persistence of RCP motor intemal voltage which gradually decays. 2 Intentional undervoltage Intentional delay, provided by an adjustable time delay function in the relay delay RCP undervoltage relay, to prevent spurious reactor trips due to short term variations in bus voltage. 3 logic delay The delay from the instant the RCP undervoltage relay timer function output contacts change state tmtil a trip signal appears at the reactor trip I circuit breaker. 4 Reactor trip circuit The delay from the instant the logic signal commanding a trip is received breakers delay at a reactor trip circuit breaker until the time when the circuit breaker contacts open. t l 5 Rod Cluster Control The delay from the openmg of a reactor trip circuit breaker until the j Assembly (RCCA) release of the associated RCCA grippers. j release delay i Evaluation of the impact on the RCP motors due to possible operation at voltages exceedmg i 10% of motor rated voltage is outside the scope of this calculation. i i i 1

Calc. For React:r Coolent Pump Internal Voltag3 Calc. N2. 09334281-01 W '" Decay on Loas of A01/A02 4kV Bus Voltage Rev.1 Date X Safety-Related l Non Safety-Related Page 6 of 28 Client Wisconsin Electric Prepared by Date Project Point Beach Units 1 & 2 Reviewed by Date ' Proj. No. 09334 281 Equip. No. Approved by Date N E, INPUT DATA A. Reactor Coolant Pump (RCP) and Motor 1. Reactor Coolant Pump: The RCPs are centrifugal pumps (Reference XII.T). A typical Speed-Torque Curve for Centrifugal Pumps (Reference ~' i') which expresses load torque reqturements as a percent of full load toique will be usal to deternane torque-speed charactenstics for 8 I the RCP ptunps. ~ Imd torque at synchronous speed (cold loop) 31,400 A-lbs (Ref XII.G) Load torque at synchronous speed (hot loop) 23,200 A-Ibs (Ret XII.G) 2. Reactor Coolant Pump Motor i Rated voltage 4000 volts (Ref XII.T) Base power 4476 kW (Ref. XII.G) Base voltage (line to neutral) 2309 volts (Ref. XII.G) Base current 646.1 Areperes (Ref. XII.G) Base impedance 3.574 ohms (Ref XII.G) l Primary (stator) resistance @ 95*C (R ) 0.00451 pu (Ref XII.0) Primary (stator) reactance (X,) 0.1042 pu (Ret XII.G) Secondary (rotor) resistance, runnmg (R ) 0.0079 pu (Ref XII.G) 2 Secondary (rotor) reactance (X ) 0.0977 pu (Ref XII.G) 2 [ Magnetizing reactance (X,) 4.878 pu (Ref XII.0) Open circuit A.C. time constant (t.,) 1.661 seconds (Ref XII.G) l Perfonnance data when pumping hot coolant: Power input 3,%2 kW (Ref. XII.T) Speed 1,191 rpm (Ref XII.T) l Performance data when pumping cold coolant: Power input 5,280 kW (Ref. XII.T) Speed 1,183 rpm (Ret XII.T) 3. Reactor Coolant Pump and Motor combined: Inertia (WK2) 70,100 lb-A8 (Ref. XII.G) i

Calc. For Reactor Coolant Pump Internal Vcitag3 Calc. Ns. 09334281-01 L.anwue Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date X Safety-Reisted l Non-Safety-Related Page 7 of 28 Client Wisconsin Electric Prepared by Date Project Point Beech Units 1 & 2 Reviewed by Date Proj. No. 09334 281 Equip. No. Approved by Date M INPUT DATA (continued) B. Unit 14160 volt bt,v:s 1 A01 and 1 A02, Unit 2 4160 volt buses 2-A01 and 2-A02 undervoltage relays and potential transformers 1. Potential Transformers 'Ibe tums ratio of the RCP supply bus pts are 35 (Reference XII.D and XII.L). 2. ABB 27D Undervoltage relays a. The designation for these relays is as follows (Reference XII.D): Unil Dus Relay designation 1 1-/_01 1273/A01 I l 274/A01 1-A02 1-273/A02 1274/A02 2 2-A01 2-273/A01 2-274/A01 2 A02 2-273/A02 2-274/A02 b. The relays are ABB (formerly known as ITE and BBC) Type 27D, Catalog Number 211R6175 (Reference XII.E). c. The maximum intentional undervoltage relcy delay for 273/274 series (including tolerances) is 0.559 seconds (result TD ATSP + TDAF taken from Page 27of A 30 &$ 4/>A d. (deleted) c. (deleted) f. Two output contacts of each undervoltage relay are connecW to the Reactor Trip logic, one output contact to Train A and one output contact to Train B (References XII.R and XII.N. Assumption V.B.1). g. The undervoltage relay output contacts are closed when bus voltage is ateve the relay setpoint 2 (Reference X11.1). h. (deleted) l b___________-______-

Calc. For Reactor Coolant Pump Internal Vcitag3 Calc. N3. 09334281-01 w-W"* Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date X Safety-Related Non-Safety-Related Page 8 of 28 Client Wisconsin Electric Prepared by Date Project Point Beach Units 1 & 2 Reviewed by Date ProJ. No. 09334-281 Equip. No. Apprcved by Date ' E INPUT DATA (continued) i. (deleted) l l j. (deleted) k. (deleted) 3. (deleted) C. (deleted) D. Reactor Trip Logic 1. The output contacts of the RCP supply bus undervoltage relays are connected to Westinghouse Model BFD relays in the Reactor Trip logic such that the BFD relays are energized when the RCP supply bus voltage is above the undervoltage relay setpoint (Section IV.B.2.f and IV.B.2.g, Reference XII.N, Assumption V.B.1). 2. Output contacts from the BFD relays of Section IV.D.1 above are connected to a second stage of BFD relays in the Reactor Trip logic such that the second stage of BFD relays are energized when the RCP supply bus voltage is above the undenoltage relay setpoint (References XII.AE, XII.N and XII.0, Assumption V.B.1). l 3. Output contacts from the second stage of BFD relays of Section IV.D.2 above are connected to l actuate the Reactor Trip circuit breakers (Reference XII.O. Assumption V.B.1). i 4. As described in Sections IV.D.2 and IV.D.3 above, the two stages of BFD relays in the Reactor Trip l legic are de-energized (drop-out) when the RCP supply bus voltage drops below the undervoltage relay setpoint (Reference XII.AE). ) i i E. Westinghouse modelBFD relay: 1. The drop-out time is less than 0.020 seconds (References XII.AE and XII.K). i l

  • W y,q.

Calc. For React:r Coolant Pump Internal Vcitag3 Calc. N2. 09334281-01 - L'#$f

  • Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date X

Safety Related Non Safety-Releted Page 9 of 28 Client Wisconsin Electric Prepared by Date Project Point Beach Units 1 & 2 Reviewed by Date Proj. No. 09334 281 Equip. No. Approved by Date M INPUT DATA (continued) F. Reactor trip circuit breakers: Reactor trip and bypass circuit breakers trip times during testing from 1984 through 19% are tabulated and attached (Reference XII.M). G. Rod Cluster Contml Assembly (RCCA): The RCCA release delay is 0.150 seconds (Reference XII.Q). l 1 ASSUMPTIONS A. Assumptions requiring VeriScation (none) B. Assumptions not requiring Verification I 1. Due to the similarity between Unit I sad Unit 2, it is reasonable to assume that the RCP supply bus undervoltage scheme for Unit 2 is the same as for Unit 1 (Reference XII.B and XII.D). 2. The synchronous speed of an RCP motor is assumed to be 1,200 rpm. This may be demonstrated by observing that the speed of the RCP under load is 1,188 rpm (when pumping cold reactor coolant) or j 1,191 rpm (when pumping hot reactor coolant) (Reference XII.T). f 3. In this calculation, RCP motor shaA output power is held constant when termmal voltage is increased l from 4,000 volts (rated voltage) to 4,576 volts (114.4% rated voltage). In reality, the shaft output i power would increase in response to the voltage increase. Using a smaller load at a given terminal voltage results in a greater calculated internal motor voltage, which is conservadve in the context of this calculation. l l This concept is illustrated in the calculations of Attachments B and D, utere it is demonstrated that l when an induction motor (motor temunal voltage being held constant) drives a pump under two dtfrerent load conditions (such as hot reactor coolant and cold reactor coolant), the lower load condition (bot reactor coolant) will result in the greater motor intemal voltage. 4. (deleted), l

Calc. For Reactor Ccolant Pump internal Vcitag3 Calc. N r. 09334281-01 , W"

  • Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date X

Safety-Related Nor; Safety-Related Page 10 of 28 Client Wisconsin Electric Prepared by Date Project Point Beach Units 1 & 2 Reviewed by Date ProJ. No. 09334-281 Equip. No. Approved by Date r~ fL ASSUMPTIONS (continued) 5. (deleted) 6. (deleted) 7. (deleted) 8. The maximum expected operating voltage on 4,160 volt buses 1-A01,1 A02,2-A01, and 2-A02 is assumed to be 110% of the switchgear nommal rating,110% of 4,160 volts = 4,576 volts. YL ACCEPTANCE CRITERIA Because the purpose of this calculation is to develop an analytical limit voltage, there is no acceptance criteria. 4 !t i l i

1 Calc. For React:r Coolant Pump intomal Vcitag) Calc. N3. 09334201-01 1 W"* Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date X Safety-Related Non Sefety-Related Pege 11 of 28 Client Wisconsin Electric Prepared by Date l Project Point Beach Units 1 & 2 Reviewed by Date ProJ. No. 09334-281 Equip. No. Approved by Date VII. MET 110DOLOGY The sequence of the calculation steps will be: determme the manmum expected time delay associated with each ofitems 2,3,4, and 5 in the table above (Section III). subtract these maximum expected time delays from the 1.5 second maximum reactor trip response time to obtain the manmum allowable time for item I in the table above (Section IID. Determme the RCP motor intemal voltage at the end of the manmum allowabic time for item I in the table above (Section III). Determme the analytical limit voltage for the RCP bus undervoltage relay setpoint. ~ A. Intentional undervoltase relav delay: ~ The maximum intentional undervoltage relay delay will be taken from Reference XII.AG (See Input Data IV.B.2.c). L l t f I e l L_---_ - --- -

Calc. For Reactir Co:lant Pump internal Vcitag3 Calc. No. 09334281-01 W L "' Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date X Safety-Related Non-Safety-Related Page 12 of 28 Client Wisconsin Electric Prepared by Date Project Point Beach Units 1 & 2 Reviewed by Date Proj. No. 09334-281 Equip. No. Approved by Date VL METHODOLOGY (continued) B. Egaetor Trio Logic delay; ne operation of the RCP supply bus undervoltage relays resulting in a reactor trip is described in Input Data l Sections IV.B.2.f, IV.B.2 g, and IV.D. In the Reactor Trip legic are two Westinghouse BFD relays in series. ne operating time associated with these relays will be determmed and used to calculate the total Reactor Trip Logic delay. C. Reactor trio circuit breakers delay: For the reactor trip and bypass circuit breakers, historical test data will be used to develop a conservative ma'ximum expected trip time (see input data Section IV.F). D. Rod Cluster Control Assembly (RCCA) release dels.y: Data from Westinghouse is available for the RCCA release delay. E. Maximum allowable transient vol'ase decay time: 1 As described above in the Overview portion of this Methodology section, the maximum expected time delay associated with each ofitems 2,3,4, and 5 in the table above will be subtracted from the 1.5 second maximum reactor trip response time to obtain the maxunum allowable time for the transient voltage decay (item 1 in the j ' table in Section III above). l F. Determination of RCP motor internal voltase at end of the maximum allowable transient voltase decay time: ll After a loss of supply bus voltage, the RCP motor intemal voltage will decay due to three factors: I j The RCP motor intemal voltage will cause electric current to flow in the magnetizing and rotor portions l of the induction motor equivalent circuit, resulting in losses in the motor internal resistances. This effect will be accounted for in this calculation. { ne RCP will slow down (decreasing rpm) due to giving up energy to pump reactor coolant, and the e RCP motor intemal voltage is directly proportional to the rpm (Reference XII.U.1). This effect will be accounted for in this calculation. ne feeder circuit breaker for the RCP motor and the feeder circuit breakers for other motors supplied fnxn the bus will remain closed until after the bus undervoltage relay is actuated and its internal timer times out (Reference XII.R indicates that the undervoltage relay output contacts are connected only to the Reactor Trip Imgic). The RCP has a high inertia which acts to store rotational energy (Input Dats IV.A.3). Due to this high inertia, the RCP will not slow down as fast as the other motors connected to the bus. Because of this difference in the rate of rpm loss, the RCP will act as a net energy supplier (induction generator) to the other motors. His action as an induction generator will cause the C___-_____

Celc. For Reactor Coolent Pump Intemel Vtitage Celc. Ns. 09334281-01 k -- w= W "* Decey on Loss of A01/A02 4kV Bus Voltage Rev.1 Date ^ l Non-Sefety Related Page 13 of 28 X Safety-Related Client Wisconsin Electric Propered by Date ] Project Point Beech Units 1 & 2 Reviewed by Date ,ProJ. No. 09334-281 Equip. No. Approved by Date t V1 METHODOLOGY (continued) l l internal voltage of the RCP motor to decay at a rate faster than accounted for by the two mechanisms i described above. However, this aspect ofRCP motor internal voltage decay will be neglected, providing an element of conservatism to this calculation. The first two effects described above are discussed in more detail below. 1. Voltane decay due to losses in RCP motor internal resistances: The steps in this process are: Using an induction motor equivalent circuit with input data for the RCP motor, calculate the shaft output power when operating at rated voltage for two cases: Case I - When the RCP is pumping cold reactor coolant. Case II - When the RCP is pumping hot reactor coolant. Determme the maximum expected voltage at the RCP motor supply bus before the postulated loss of voltage. Calculate the RCP motor internal voltage when operating at the maximum expected voltage e before the postulated loss of supply bus voltage, for Cases I and II described above. l Using the greater of the RCP motor internal voltages calculated in the presious step, calculate the e decay of the RCP motor internal voltage after the postulated loss of supply bus voltage. i The above steps are desenbed in more detail below. t t i f C__________________

Calc. For React:r Coolant Pump intomal Vcitag3 Calc. Ns. 09334281-01 W "* Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date l X Safety-Related Non Safety-Related Page 14 of 28 Client Wisconsin Electric Prepared by Data Project Point Beach Units 1 & 2 Reviewed by Date ProJ. No. 09334 281 Equip. No. Approved by Date t M METHODOLOGY (continued) a. Using the equivalent circuit for an induction motor (Reference XII.U.2) and data for the RCP motor, the RCP motor shaft output power will be calculated when operating with motor rated voltage applied to the motor terminals for Cases I and II. 1. The following formulas will be used with the input data and RCP motor rated voltage to demonstrate that the input data reflects operation at RCP motor rated voltage. n,,- n,,, n,, Where: s = slip n,,,, = synchronous speed n, = mechanical shaft speed ofrotor Z,,,, = R, + jX, Z,,,, = jX,,, R l Z,,,= ( * + jX,) 8 1 f y" ", (Zwr w (2,.d y** l Z +Z r ma m raw h /m(Z"*) 0"* = arctan( Re(Z,,,,,,,,)) i P, = l v'*""l 2 cos(0,,,,,) (3) s { ~ l

Calc. For React:r Coolant Pump Internal Vcitag) Calc. Ns. 09334281-01 -- W -- W "* Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date l Non. Safety-Related Page 15 of 28 X Safety-Related Client Wisconsin Electric Prepared by Date i Project Point Beach Units 1 & 2 Reviewed by Date Prol. No. 09334-281 Equip. No. Approved by Date E METHODOLOGY (continued) 1 ii. The following formulas will be used to calculate the RCP motor intemal voltage. V,,,,

  • V,,,,4 (Same as Vw)

I, = Z_ E, = V,,,,,, - (/,)(2,,,) ~ iii. The following formulas will be used to calculate the RCP motor shaft output power. Im(2,,,,,) 0'*'" = arctan( Re(Z,,)) IE,l8 P,,, = cos(0,,,,) (3) rota i P,,,, = P,,,, ( 1 - s) b. A value for the maximum expected voltage at the RCP motor 4160 volt supply bus before the postulated loss of voltage will be determmed. This bus voltage will be referred to as Vwin this calculation. I e i -_-______________m_

Calc. For Reactor Coolant Pump Intemal Vcitag3 Calc. N3. 09334281-01 --- W "* Decay on Loss of A01/A02 4kV Bus Voltage = Rev.1 Date I X Safety-Related l Non-Safety-Related Page 16 of 28 Client Wisconsin Electric Prepared by Date l ProJoct Point Beach Units 1 & 2 Reviewed by Date 1 Proj. No. 09334 281 Equip. No. Approved by Date , M METHODOLOGY (continued) The RCP motor internal voltage wwnding to operation with V (from Section VII.F.1.b) c. will be calculated for Cases I and II. It is assumed that when the motor ternunal voltage is increased, the motor shaft output power will not increase (Assumption V.B.3). The RCP motor shaA output powe~ calculated above 3 (Section VII.F.1.a.iii) will be used. I. The following fonnulas will be used to calculate the RCP motor internal voltage during operation at V. A,nc ~ A s m ayrw I Where: s = slip n., - synchrmas speed n, = mechanical shaA speed of rotor Note: The value of n, will be selected such that the RCP notor shaft output power calculated below agrees with the value calculated in step VII F.1.a above. Z,,,, = R, + jX, Z,,,,,,,m = jX,,, t R This value will be different than in Z,,,=( 2 + /X ) SectionVII.F.1.a above because the 2 value of s is different. Z"'** = (Z""''"') (Z,,,,) Z .,,.r, + Z.w m i y = A j ) /, a Z,,,,,,, C__

Calc. For React:r C;olant Pump Intemal Vcitags Calc. N3. 09334281-01 - ' - - 'b M'" Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date - 7 X Safety-Related Non Safety-Related Page 17. of 28 Client Wisconsin Electric Propered by Date Project Point Beach Units 1 & 2 Reviewed by Date Prol. No. 09334-281 Equip. No. Approved by Date V1 METHODOLOGY (continued) 1 E, = V - (/ )(Z,,,) 3 i I ii. The following fonnulas will be used to calculate the RCP motor shaft output power. l Im(ZJ 0"'" = arctan(Re(Z,,)) lE,l2 P,,,,= cos(0J (3) I,I l P = P,,,, (1 - s) 4 o I i i l t i l Y e h--________m

Calc. For React:r Coolant Pump Intemal Vcitaga Calc. Ns. 09334281-01 E N'" Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date l Non-Safety-Related Page 18 of 28 X Safety-Related Client Wisconsin Electric Prepared by Date l Project Point Beach Units 1 & 2 Reviewed by Date Proj. No. 09334-281 Equip. No. Approved by Date M METHODOLOGY (continued) 1 l l d. Using the highest of Case I or II RCP motor intemal voltage before the postulated loss of voltage, the RCP motor intemal voltage at the end of the maximum allowable transient voltage decay time will be calculated in two ways: i. 'Ihe RCP motor intemal voltage will be calculated at the end of the maxunum allowable transient voltage decay time desenbed in VII.E above, and ii. A graph of RCP motor internal voltage during the first 1.5 seconds after the postulated loss of voltage will also be developed Based on the definition of any time constant, the fonnula used to calculate the RCP motor intemal voltage after the postulated loss of voltage is: -t '-1 V,,,, = (E,) e '= 1 time after the postulated loss of voltage, in seconds. Where: t = RCP motor open circuit time constant. t, = o the RCP motor intemal voltage correspondmg to operation at E = i maximum expected supply bus voltage before the postulated loss of voltage, calculated in VII.F.1.c.i above. f l V,,,, the RCP motor internal voltage and temunal voltage at any = I time "t" after the postulated loss of RCP motor supply bus voltage. As described at the beginning of VII.F above, the current outflow fmm the RCP motor to other motors 3 connected to the same bus is being neglected Therefore, the l RCP motor internal voltage and ternunal voltage are taken to l be the same, which is conservative for the purpose of this calculation. 2. Voltane decev due to decreasine RCP motor mm: Refer to the induction motor equivalent circuit (Reference XII.U.2) for the following discussion. After g the postulated loss of supply bus voltagc, there will no longer be an emf to force current to flow into the stator winding of the RCP motor. As discussed in at the beginning of Section VII.F above, the RCP motor will act as a generator to other motors connected to the bus. Any current flowing in the stator winding will be out to other motors The RCP motor will only der: lop motor output torque when current is flowing into the stator wmdmg. When current flows out of the stator winding (RCP motor acting as an induction generator), braking occurs which is conservatively neglected in this calculat.%

Calc. For Reactor Coolant Pump Intemal Vcitag3 Calc. N2. 09334281-01 W"

  • Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date X

Safety-Related Non Safety-Related Page 19 of 28 Client Wisconsin Electric Prepared by Date Project Point Beach Units 1 & 2 Reviewed by Date Proj. Nc. 09334 281 Equip. No. Approved by Date M METHODOLOGY (continued) To calculate pump and motor deceleration, the method in Sargent & Lundy Standard ESC 307 (Reference XII.V) will be used. RCP deceleration will be divided into intervals of decreasing speed. For each interval of speed decrease, the RCP deceleration time will be calculated based on the speed-torque characteristics of the driven equipment and the inenia of the pump and motor. From ESC-307, the time required to. accelerate or decelerate a load through a speed increment is given l by the following equation: ARPMx WK* 308 x Ty I (

  • Vhere:

RPM is the spced interval. WK2 is the total inertia of the motor and load in Ib-ft8 f T,, is the net accelerating torque (motor output torque less torque required by the I load) during the speed interval, in Ib-ft. T is time requird for the motor to accelerate the load through the speed interval. ) The accumulated deceleration time is the sum of the deceleration for the individual RPM time intervals startmg at fullload RPM. l Tr.,,, = E A T s l 3. Combininc the effects of RCP motor internal voltane decay due to intemal resistances and decreasing i RPM: i In the precedmg section VII.F.2, the amount of deceleration during the maxunum allowable transient 4 voltage decay time (from Section VII.E) may be determmed as a percent of full load rpm. The RCP motor internal voltage associated with VII.F.1.c.i above may be decreased by that percentage because the internal voltage is directly proportional to the rpm (Reference XII.U.1). l j O. Determination of the anahtical limit voltane for the RCP bus undervoltace relay setroint: l The RCP motor internal voltage from VII.F.3 above will be used as the analytical limit voltage for the RCP bus i undervoltage relay setpoint. His will be a conservative value because it does not include any voltage drop through the RCP stator impedance due to current outflow to other motors, nor does it include the more rapid speed (and therefore voltage) decay due to the braking action of other motors connected to the RCP motor supply bus, -)

Calc. For React:r Coolant Pump Internal Vcltag3 Calc. No. 09334281-01 r- - W'" Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date ~ X Safety-Related Non-Safety-Related Page 20 of 28 l Client Wisconsin Electric Prepared by Date Project Point Beach Units 1 & 2 Reviewed by Date ProJ. No. 09334-281 Equip. No. Approved by Date V[II, CALCULATION 3 and RESULTS The various calculations will be performed as described in the Methodology Section (Sec' tion VII). A. Intentional undervoltane relav delay: he max 2 mum undervoltage relay delay is 0.559 seconds (Input Data IV.B.2.c). B. Reactor Trin Locic delay: l The drop-out time of a Westinghouse BFD relay is less than 0.020 seconds (Input Data IV.E.1). As described in Section VII.B the total logic delay involves two BFD relays in series. Herefore, the total logic delay will be less than 0.040 seconds For conservatism, 0.040 seconds will be used. l C. Reactor trio circuit breakers delay: An examination of histoncal test data for the reactor trip and bypass circuit breakers (see input data Section IV.F) indicates tha' trip time during annual testing has been 5 cycles (0.083 seconds) or less since 1984, with the single exception of one bypass breaker in 1984 for which a 6 cycle (0.100 seconds) test time was recorded. In this calculation, a maximum expected trip time delay of 0.100 seconds will be used for the reactor trip circuit breakers. This is considered to be conservative in that it is greater than any trip times during testing j recorded in the past ten years. i l D. Rod Cluster Control Assembly (RCCA) release delay: i 0.150 seconds will be used for the RCCA release delay (Input Data IV.G). E. Maximum allowable transient voltace decav: The maxunum allowable transient voltage decay time is calculated as follows: 1.500 seconds maximum reactor trip response time 0.559 seconds intentional undervoltage relay delay (including maximum possible error) j 0.040 seconds logic delay 0.100 seconds reactor trip circuit breakers delay - 0.150 seconds RCCA release delay l 0.651 seconds maximum allowable transient voltage decay 1 l u_____________________

I Calc. For Reactor Coolant Pump Internal Vcitag3 Calc. N2. 09334281-01 { W" Decay on toss of A01/A02 4kV Bus Voltage Rev.1 Date l Non-Sofety-Related Page 21 of 28 X Safety-Related Client Wisconsin Electric Propered by Date j Project Point Beach Units 1 & 2 Reviewed by Date ProJ. No. 09334 281 Equip. No. Approved by Date l Vill. CALCULATIONS and RESULTS (continued.1 i F. Determination of RCP motor intemal voltage at end of maximum allowable transient voltane decav: 1. Voltane decay due to losses in RCP motor intemal resistances: RCP motor intemal voltage before the postulated loss of voltage: a. De equivalent circuit for an induction motor (Reference XII.U.2) will be used to implement the calculations described in Section VH.F.1.s above. De actual calculations were performed in MathCad (Reference XH.W), and are included as Attachments to this calculation. The following table summanzes the calculations performed. I Applicable Awhment , Calculatal i Methodology with RCP motor Operating Mode. Calculation Description Sectmn . Calculation ~ intemal s voltage 'f Case I-Cold Demonstrate that input data reflects VII.F. I.a Attachment B Reactor Coolant operation at RCP motor rated voltage, and calculate shaft output power. Calculate RCP motor intemal voltage VB.F.1.b Attachment C 4399.8 l correspondmg to operation at maximum and volts l expected bus voltage V (4576 volts). VH.F.1.c f Case II-liot Demonstrate that input data reflects VIII.l.a Attachment D l Reactor Coolant operation at RCP motor rated voltage, I and calculate shaft output power. Calculate RCP motor internal voltage VH.F.1.b Attachment E 4432.2 correspondmg to operation at maximum and volts expected bus voltage V (4576 volts). VII.F.1.c Of the above two cases, Case II (Hot Reactor Coolant) results in the greater calculated RCP i motor internal voltage before the postulated loss of voltage. It may also be observed that higher load torque associated with Case I (Cold Reactor Coolant) will cause the RCP to decelerate more quickly than for Case H (Hot Reactor Coolant). As noted in Section VII.F.3, motor intemal voltage after loss of RCP supply bus voltage is proportional to the speed. For the purpose of this l calculation, a greater intemal voltage is conservative. Derefore, the calculated value of RCP i motor intemal voltage corres;xmdmg to Case II (Hot Reactor Coolant) above will be used in j subsequent sections of this calculation. j

Calc. For Reactor Coolant Pump Intemal Vcitag3 Calc. ND. 09334281-01 W"* Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date X Safety-Related Non-Safety-Related Page 22 of 28 Client Wisconsin Electric Prepared by Date Project Point Beach Units 1 & 2 Reviewed by Date Prol. No. 09334-281 Equip. No. Approved by Date Vllt. CALCULATIONS and RESULTS (continued) b. Maximum expected voltage at the supply bus before the postulated loss of voltage: The maximum expected voltage at the 4160 volt supply buses associated with the RCP motors is 4,576 volts (Assumption V.B.8). c. Calculation of RCP motor internal voltage at the end of maxunum allowable transient voltage decay time: The RCP motor intemal voltage at the end of maxunum allowable transient voltage decay time (as desenbed in Section VII.F.c above) is calculated using MathCad (Reference XILW), and is included in Attachment F. The value obtained is 2,995.1 volts. ( i l i i i t i ,k I 1 I l-

f I Calc. For React r Coolant Pump Intemal Vcitag3 Calc. Ns. 09334281-01 I l 'W"* Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date X Safety-Related Non-Safety-Related Page 23 of 28 { Client Wisconsin ElectrS Prepared by Date Project Point Beach Units 1 & 2 Reviewed by Date ProJ. No. 09334-281 Equip. No. Approved by Date Vill. CALCULATIONS and RESULTS (continued) l 2. Voltare decav due to decreasing RCP motor rom: 1 The calculated motor and pump deceleration times were determmed by applying the equations of Section VII.F.2 in an EXCEL (Reference XII.X) spreadsheet, which are included in Attachment G. The motor and load data on the spreadsheet is taken from Section IV of this calculation. De contents of each spreadsheet column are determmed as follows: Column N3mk Explanation ' (1) Speed at the beginning of the speed inu:rval, expressed as a percentage of the full load speal (2) Speed at the beginning of the speed interval, conespondmg to Column Number i except expressed as RPM. (3) Speed at the end of the speed inten al, expressed as RPM. (4) The magnitude of the speed intenal in RPM (Column 3 minus Column 2). This { conesponds to the A RPM term in the equation for A T in Section VII.F.2. 1 (5) From Reference XII.Y, the torque required by the RCP at the start of the speed inten a!, j expressed as a percentage of the full load torque. (6) ne torque (in Ib-ft) required by the load at the start of the speed interval. Calculated by multiplying Column 5 by the full load torque. l (7) Net decelerating torque as described in the equation for A T in Section VIIF.2). Because there is no external voltage applied to the RCP motor terminals, the net decelerating I torque is the same as the load requirement (Column 6). (Negative numbers represent a decelerating condition.) (8) Time to decelerate through the speed interval,in seconds. Calculated using first equation in Section VII.F.2. (Negative numbers represent a decelerating condition.) (9) Cumulative time to decelerate the load. Calculated using the second equation in Section VII.F.2. (Negative numbers represent a decelerating condition.) As may be seen from the tabulation in Attaciunent G, at the end of 0.64 seconds, the RCP has f decelerated to 95.0% of full load speed, and at the end of 0.66 seconds, the RCP has decelerated to 94.8% offullload speed Usinginterpolation:

4 I Calc. For React:r Coolant Pump Intemel Vcitage Calc. N3. 09334281-01 W "" Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date O X Safety-Related Non Safety Related Page 24 of 28 V's Client Wisconsin Electric Prepared by Date Project Point Beach Units 1 & 2 Reviewed by Date Prof. No. 09334-281 Equip. No. Approved by Date Vill. CALCULATIONS and RESULTS (continued) 95.0% - 94.8%, 95.0% - X 0.64 - 0.66 0.64 - 0.651 Solving for X: X = 94.89% s As may be seen from the tabulation in Attachment G and the above interpolation, at the end of the maximum allowable transient voltage decay time (0.651 seconds), the RCP has decelerated to 94.89% of fullload speed. 3. Combinine the effects of RCP motor internal voltase decav due to intemal resistances and decreasing RPM: As calculated in VIII.F.1 above, the RCP motor internal voltage decays to 2,995.1 volts at the end of the maxunum allowable transient voltage decay time as a result oflosses in intemal resistances alone. As calculated in VIII.F.2 above, the RCP motor speed will decay to 94.89% of the full load speed at the end of the maximum allowable transient voltage decay time. I J The RCP motor intemal voltage at the end of the maxunum allowable transient voltage decay time as a l result of both effects will be: t (2,995.1)(94.89%) = 2,842.1 volts G. Detennination of the anahtical hmit voltase for the RCP bus undervoltase relay setnoint: I i As described in Section VII.G, the analytical limit voltage for the RCP bus undervoltage relay setpoint will be taken to be the RCP motor intemal voltage at the end of the maxunum allowable transient voltage decay time, or 2,842.1 volts. f l

Calc. For React:r Coolant Pump intomal Vcitags Calc. No. 09334281-01 1 *' Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date X Safety-Related l Non Safety-Reisted Page 25 of 28 Client Wisconsin Electric Prepared by Date Project Point Beach Units 1 & 2 Reviewed by Date Prol. No. 09334-281 Equip. No. Approved by Date 11 COMPARISON of RESULTS with ACCEPTANCE CRITERIA (not applicable) CONCLUSIONS The analytical limit voltage for the RCP bus undervoltage relay setpoint is 2,842.1 volts. In the Point Beach Nuclear Unit Technical Specifications (Reference XII.C), RCP motor 4160 volt supply bus undervoltage is defined as less than 75% of normal voltage. This corresponds to less than 3,120 volts, (with normal voltage dermed as 4,160 volts). The analytical limit derived in this calculation is approximately 278 volts lower than 3,120 volts. XL RECOMMENDATIONS (none) 9 64

Calc. For Reactor Coolant Pump Internal Voltage Calc. No. 09334281-01 L"*% "

  • Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Dete

"- w-X Safety-Related Non-Safety-Related Page 26 of 28 Client Wisconsin Electric Prepared by Data Project Point Beach Units 1 & 2 Reviewed by Date ProJ. No. 09334-281 Equip. No. Approved by Date XIL REFERENCES A. Point Beach Final Safety Analysis Report (FSAR): 1. Section 14.1.8, pages 14.1.8-1 and 14.1.8-2, dated June,1994. 2. Table 14.1.8-1. 3. Table 14 3. B. Wisconsin Electric Drawing E-1, Revision 12," Single Line Diagram, Station Connections", C. Point Beach Technical Specifications, Section 15.2.3: 1. Page 15.2.3 1, Unit 1/ Unit 2, dated May 1973/ March 1973

2..

Page 15.2.3-2, Unit 1, Amendment No.156/ Unit 2, Amendment 160, dated October 28,1994 3. Page 15.2.3-3, Unit 1, Amendment No.142/ Unit 2, Amendment 146, dated October 27,1993 4. Page 15.2.3 3a, Unit 1/ Unit 2, dated May 1973/ March 1973 (Indicates the accident analysis for CLOF assumes a maximum reactor trip re3xmse time of 1.5 seconds.) .~ D. Drawing E-11, Sheet 2, Revision 7, (Bechtel Job No. 6118)," Schematic Meter & Relay Diagram 4160 V l Auxilia.'y System". [ E. Wisconsin Electric Champs database (Screen prints of data for Unit I and Unit 2 4160 volt bus A01 and A02 g undervoltage relays.) f l (Indicates that the undervoltage relays shown on Reference H are ABB 27D. Included in j Attachment A.) i I F. WEP-76-536, Letter from Westinghouse to J. R. Wilson, dated August 12,1976. (included in Attachment A.) l G. GMT-94-3, letter from Westinghouse, Generator / Motor Technology Group, dated March 9,1994. (Included in Attachment A.) IL (deleted) 1. Control Tech. Manual BBC-405, ASEA BROWN BOVERI (ABB) IB 18.4.7-2, Issue E. " Instructions, Undervoltage Relays and Overvoltage Relays". (Instruction Bulletin for Type 27D undersoltage relays.) l \\ l 1

Calc. For Reactor Coolant Pump Internal Vcitag3 Calc. N3. 09334281-01 ~ W"* Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date X Safety-Related Non Safety-Related Page 27 of 28 J Client Wisconsin Electric Prepared by Date Project Point Beach Units 1 & 2 Reviewed by Date Prol. No. 09334-281 Equip. No. Approved by Date J. (deleted) K. Westinghouse brochure, Class 1E, NBFD Nuclear Control Relays, RCS/PS-5-1191-17815.8. L. Westinghouse Drawing 499B466 Sh. 202 Rev.13. M. FAX, J. McDermid (WEPCo) to R. liigdon (S&L), dated 06/1997,"Undervoltage Analytical Limit Calculation Information", and tabulations of Reactor trip and bypass circuit breakers trip times during testing from 1984 through 1996 from RMP-26," Reactor Trip arxi Bypass Breaker Maintenance" The tabulations were attached to WEPCo Calculation 954095, Rev.1 (Reference XII.AE) and a draft of Rev. 2 to the same calculation. ~ (Included in Attachment A.) N Westinghouse Drawing 617F354, Sh.10, Rev.18. O. Westinghouse Drawing 617F354, Sh. 4, Rev. 7. P. Wisconsin Electric Design and Installation Guideline DO-101," Instrument Setpoint Methodology", Rev.1, September 12,1995. Q. Wenghse Technical Bulletin 92-03,"Undervoltage Trip Protection", dated 5/15/92. (Includedin Attachment A.) f R. Westinghouse Drawing 499B466, Sh. 203, Rev. 9. S. ' Westinghouse Drawing 499B466. Sh. 205, Rev.10. T. Component Instruction Manual #00102," Reactor Coolant Pump" (Included in Attachment A.) U. Electric Machmery. fifth edition, by A. E. Fitzgerald, Charles Kingsley, Jr., and Stephen D. Umans, copyright 1990 by McGraw-liill, Inc. ISBN 0-07-021134-5. 1. Equation 4-47 on page 182 indicates that induction motor intemal (rotor) voltage is directly Proportional to the rpm. i 2. Pages 332 and 333, induction motor equivalent circuits. I

1 l Calc. For Reactor Coolant Pump Internal Vcitag3 Calc. Ns. 09334281-01 W "* Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date X Safety-Related Non-Safety-Related Page 28 of 28 Client Wisconsin Electric Prepared by Date Project Point Beach Units 1 & 2 Reviewed by Date l Proj. No. 09334-281 Equip. No. Approved by Date V. Sargent & Lundy Standard ESC-307," Electrical Engmeenng Reference for Checking Voltage Drop in Starting i I A-C Motors", dated 1 244. W. MathCad, Version 4.0 (Sargent & Lundy Computer Program No. 03.7.548-4.0). This programis controlled by the Sargent & Lundy Facilities and Operations Division. Documentation and validation for this program are maintained in the Sargent & Lundy software library. X. Microsoft EXCEL, Version 5.0 (Sargent & Lundy Computer Program No. 03.1.138-5.0). This program is controlled by the Sargent & Lundy Facilities and Operations Division. Calculations created using EXCEL are reviewed as if manually-prepared. Y. Speed-Torque Curve for Centrifugal Pumps, Louis Allis Curve # 182%, dated 11/6n5. (Includedin Attachment A.) Z. (deleted) AA. (deleted) AB. (deleted) AC. (deleted) AD. (deleted) AE. "Determmation of Response Time of Reactor Trip on 4160 V Bus Undervoltage", Wisconsm Electric, Point Beach Nuclear Plant Calculation # 95-0095, Revision 1, approved 1/15/97. AF. (deleted) AG. Duke Engmeenng & Services Document (CALC) Number PBNP-IC-33, Rev. O,"4.16KV RCS Pump and Reactor Trip Undervoltage Matrix Relays Uncertamty/Setpoint Calculation". l t

I l Calc. For Reactor Coolant Pump Internal Vcitag) Calc. N1 093'J4281-01 'e E ^' Decay on Loss of A01/A02 4kV Bus Voltage Rev.1 Date 1, A I t-T X Safety Related l Non Safety-Related Page A1 of A18 'd l Client Wisconsin Electric Prepared by Date Project Point Beach Units 1 & 2 Rev!ewed,by Date ProJ. No. 09334-281 Equip. No. Approved by Date i Attachment A Miscellaneous References Reference XII.E (Wisconsin Electric Champs database). . A2 1 Reference XII.F (WEP-76-536, Letter from Westinghouse to J. R. Wilson, dated August 12,1976.). AS Reference XII.G (GMT-94-3, Letter from Westinghouse, Generator / Motor Technology Group, dated March 9, 1994.) A7 (deleted) Reference XII.M (FAX, J. McDermid (WEPCo) to R. Higdon (S&L), dated 06/19/97, and tabulations.). A8 Reference XII.Q (Westinghouse Technical Bulletin 92-03,"Undervoltage Trip Protection", dated S/15/92.). A14 Reference XII.T (Component Instruction Manual #00102, " Reactor Coolant Pump".) A17 Reference XII.Y (Speed-Torque Curve for Centrifugal Pumps, Louis-Allis Curve # 182%, dated 11/6/75.) Al8 (deleted) I l (deleted) l (deleted) I (deleted) (deleted) 1

1 1 UNIT: PB2 >>> ADD / REVISE EQUIPMENT. DATA SCREEN ! <<< System: MRR I 101 [ EQUIP ID: 273/A01 Physical Lern: 26/CB/SWGR RM 2A52-26 EQUIP NAME: 2A-01 BUS UNDERVOLTAGE RELAY PARENT / EQUIPMENT ID: TRACKING ID: PB2 273/A01-AA Text ID: PSI Text ID: Tracking Dese: 2A-01 BUS UNDERVOLTAGE RELAY Tech Manual Cti: Equip Group: RELAY Equip Type: Resp Group: MTN WO No: Mfg Code: ITE ITE CIRCUIT BREAKER CO. Vendor Code: WEST WESTINGHOUSE ELECTRIC CO. Model No: 27D Serial No: 211B6175 UNIT: PB2 >>> ADD / REVISE EQUIPMENT-DATA SCREEN I <<< System: MRR .. _.]01 EQUIP ID: 273/A02 Physical Letn: 26/CB/SWOR RM 2A52-27 EQUIP NAME: 2A-02 BUS UNDERVOLTAGE RELAY PARENT / EQUIPMENT ID: TRACKING ID: PB2 273/A02 AA Text ID: PSI Text ID: Tracking Dese: 2A-02 BUS UNt>ERVOLTAGE RELAY Tech Manual Ctt: Equip Group: RELAY Equip Type: Resp Group: MTN WO No: Mfg Code: ITE ITE CIRCUIT BREAKER CO. Vendor Code: WEST WESTINGHOUSE ELECTRIC CO. Model No: 27D Serial No: 211B6175 UNIT: PB2 >>> ADD / REVISE EQUIPMENT-DATA SCREEN 1 <<< System: MRR O -101 EQUIP ID: 274/A01 Physical Letn: 26/CB/SWGR RM 2A52-26 EQUIP NAME: 2A-01 BUS UNDERVOLTAGE RELAY PARENT /EQUIPMENTID: TRACKING ID: PB2 274/A01 AA Text ID: PSI Text ID: Tracking Dese: 2A-01 BUS UNDERVOLTAGE RELAY Tech Manual Ctl: Equip Group: RELAY Equip Type: Resp Group: MTN WO No: Mfg Code: ITE ITE CIRCUIT BREAKER CO. Vendor Code: WEST WESTINGHOUSE ELECTRIC CO. Model No: 27D Serial No: 211B6175 UNIT: PB2 >>> ADD / REVISE EQUIPMENT - DATA SCREEN 1 <<< System: MRR ]o1 EQUIP ID: 274/A02 Physical Letn: 26/CB/SWGR RM 2A52 27 EQUIP NAME: 2A-02 BUS UNDERVOLTAGE RELAY PARENT /EQUIPMENTID: TRACKING ID: PB2 274/A02-AA Text ID: PSI Text ID: Tracking Dese: 2A-02 BUS UNDERVOLTAGE RELAY Tech Manual Cti: Equip Group: RELAY Equip Type: Resp Group: MIN WO No: Mfg Code: ITE ITE CIRCUIT BREAKER CO. Vendor Code: WEST WESTINGHOUSE ELECTRIC CO. Model No: 27D Serial No: 211B6175 4 Calc. No. 09334281-01 0; .1 Page A2 of A18 Project No. 09334-281

UNIT: PBt >>> ADD / REVISE EQUIPMENT-DATA SCREEN I <<< System: MRR 101 o O EQUIP ID: 273/A01 Physical Let.r ?',/CB/SWGR RM 1 A52-01 EQUIP NAME: l A-01 B,US UNDERVOLTAGE RELAY PARENT /EQUIPMENTID: TRACKING ID: PBl 273/A01-AA e ID: PSI Text ID: Tracking Dese: l A-01 BUS UNDERVOLhvE RELAY Tech Manual Cti: Equip Group: RELAY Equip Type: Resp Group: MTN WO No: Mfg Code: ITE ITE CIRCUIT BREAKER CO. Vendor Code: WEST WESTINGHOUSE ELECTRIC CO. l Model No: 27D Serial No: 211R6175 UNIT: PB1 >>> ADD / REVISE EQUIPMENT-DATA SCREEN 1 <<< System: MRR 101 EQUIP ID: 273/A02 Physical Letn: 26/CB/SWGR RM 1 A5217 EQUIP NAME: l A-02 BUS UNDERVOLTAGE RELAY PARENT / EQUIPMENT ID: TRACKING ID: PB1273/A02-AA Text ID: PSI Text ID: Tracking Desc: l A-02 BUS UNDERVOLTAGE RELAY Tech Manual Ct!: Equip Group: RELAY Equip Type: Resp Group: MTN WO No: Mfg Code: ITE ITE CIRCUIT BREAKER CO. Vendor Code: WEST WESTINGHOUSE ELECTRIC CO. Model No: 27D Serial No: 211R6175 () UNIT: PB) >>> ADD / REVISE EQUIPMENT-DATA SCREEN 1 <<< System: MRR 101 EQUIP ID: 274/A01 Physical Lc:n: 26/CB/SWGR RM 1 A52-01 EQUIP NAME: l A-01 BUS UNDERVOLTAGE RELAY PARENT / EQUIPMENT ID: TRACKfNG ID: PBl 274/A01-AA Text ID: PSI Text ID: Tracking De.,c: l A-01 BUS UNDERVOLTAGE RELAY Tech Manual Cti: Equip Group: RELAY Equip Type: Resp Group: MTN WO No: Mfg Code: BBC BROWN BOVERI. INC. Vendor Code: WEST WESTINGHOUSE ELECTRIC CO. Model No: ITE-27D Serial No: 211R6175 UNIT: PBt >>> ADD / REVISE EQUIPMENT-DATA SCREEN 1 <<< System: MRR -101 EQUIP ID: 274/A02 Physical Lern: 26/CB/SWGR RM 1 A52-17 EQUIP NAME: l A-02 BUS UNDERVOLTAGE RELAY PARENT / EQUIPMENT ID: TRACKING ID: PBl 274/A02-AA Text ID: PSI Text ID: Tracking Desc: l A-02 BUS UNDERVOLTAGE RELAY Tech Manual Cti: Equip Group: RELAY Equip Type: Resp Group: MTN WO No: Mfg Code: BBC BROWN BOVER1, INC. Vendor Code: Model No: ITE-27D Serial No: 211R6175 ) Calc. No. 09334281-01 Rev.1 Page A3 of A18 Project No. 09334-281

UNIT: PBl >>> ADD / REVISE EQUIPMENT-DATA SCREEN 1 <<< System: MRR - f-101 EQUIPID: 273/A01 Physicalletn: 26/CB/SWGR RM I A52 01 EQUIP NAME: l A 01 BUS UNDERVOLTAGE RELAY PARENTiEQUIPMENrID: TRACKING ID: PBl 273/A01.AA Text ID: PSI Text ID: Tracking Desc: 1 A-01 BUS UNDERVOLTAGE RELAY Tech Manual Ct!: Equip Group: RELAY Equip Type: Resp Grouo: MTN WO No: Mfg Code: ITE ITE CIRCUIT BREAKER CO. Vendor Code: WEST WESTINGHOUSE ELECTRIC CO. Model No:.27D Serial No: 211R6175 UNIT: PB1 >>> ADD / REVISE EQUIPMENT-DATA SCREEN I <<< Satem: MRR ... 101 EQUIP ID: 273/A02 Physical Lctn: 26/CB/SWGR RM i A5217 EQUIP NAME: l A-02 BUS UNDERVOLTAGE RELAY PARENT /EQUIPMENTID: TRACKING ID: PBl 273/A02 AA Text ID: PSI Text ID: Tracking Desc: l A 02 BUS UNDERVOLTAGE RELAY Tech Manual Cti: Equip Group: RELAY Equip Type: Resp Group: MTN WO No: Mfg Code: ITE ITE CIRCUIT BREAKER CO. Vendor Code: WEST WESTINGHOUSE ELECTRIC CO. Model No: 27D Serial No: 211R6175 UNIT: PBl >>> ADD / REVISE EQUIPMENT. DATA SCREEN I <<< System: MRR .. 101 EQUIP ID: 274/A01 Physical Letn: 26/CB/SWGR RM i A52-01 EQUIP NAME: ! A-01 BUS UNDERVOLTAGE RELAY PARINT/EQUIPMENTID: TPACKING ID: PBI 274/A01-AA TextID: PSI Text ID: Tracking Desc: l A-01 BUS UNDERVOLTAGE RELAY Tech Manual Ctl: Equip Group: RELAY Equip Type: Resp Group: MTN WO No: Mfg Code: BBC BROWN BOVERI, INC. Vendor Code: WEST WESTINGHOUSE ELECTRIC CO. Model No: ITE-27D Serial No: 211R6175 UNIT: PBI >>> ADD / REVISE EQUIPMENT. DATA SCREEN 1 <<< System: MRR oI EQUIP ID: 274/A02 Physical Lern: 26/CB/SWGR RM i A5217 EQUIP NAME: l A-02 BUS UNDERVOLTAGE RELAY PARENT / EQUIPMENT ID: TRACKING ID: PBI 274/A02.AA TextID: PSI Text ID: Tracking Desc: l A-02 BUS UNDERVOLTAGE RELAY Tech Manual Cti: - Equip Group: RELAY Equip Type: Resp Group: MTN WO No: Mfg Code: BBC BROWN BOVERI,INC. Vendor Code: Model No: ITE 27D Serial No: 211R6175 Q Calc. No. 0933428101 W-Rev.1 Page A4 of A18 Project No. 09334-281 A-__---__-._

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'88***" WestiftEho 8 En oss mee's'*ecsos ./8 M 6tClflC C0f)2f 31!;D y. i:$ asstra S y <. s,, Nuclear Service Division WEP.76 536 ' '.H ', - August 12, 1976 l Re f: PBM-kHP.1566 i, : f'. I' i f;. Mr. J.R Wilson E h ciest Froject Administrator e' J$.".. ' Wisconsin Electric Fover Co. ?j M.. ?

  • 231 West Michigan Avense eD'.,.. titivaukee, W1stensin 53201 J:';-

<E . l.h . x4 p%/y / Dest Mr. Vilson: i 5 ;..','.74, $~I" '.. f.[ h($ =y' ',...m'ixT suen wuet.un run 7 l ?. ' f' bu/o I l UNDEnvol, TACE P!. ACTOR TP:P TtME DEIM d... ,f.. * , p., y,. l - M. .... ~.. ~n.~.... n. ?: jaN Your referenced letter expressed your desire to increase the tisce deley in the subject cirecita to at least 30 cycles and requested that you be sdvised < f,', _ y?'t'h(, as to the camisure time delay permissible This delsy, vbich represents the I combined effect of the inherent. relay delay plies,.tne intentiossi dolsy, may f f!":- ,l p !;fe'.'.a; -*dc., be increased up to 0.75 seconds..;, ty P..h;*W.'. f. r 4 # :.6,:,%.tr@ W.'??- -E-9 l;}:M,s'," 4 '..., The bests for the undervoltage cine deley is as Indica r. , sey,s::.awq % .g. c< *. v v 3 _trMDEnvet. TACE ' REACTOR C001M; FtMp It'$$ES ' y 4t .; y.g .m....,,. h';); g.,,,

  • The Undervoltage Reactor Coolant Fump bus' trips Trovida reacter core protection g.n.

sgsinst CH3 as e result of loss of voltage'to more thsa one reactor ecolant k MV '. purp.. The specified set poista sesure a reactor trip signet is generated before @tpl'77 the low flow trip set point is resched.hfine delay.is incorporated in the under-S.j.,~. volt age trip to prevent spurious reactor.' trips,from nacientary electrical povar i transients. The delay is set so that'ths ties' required for a signal to reach i ,1 ) b Ul,* ' the resetor trio breakers follovias the* simultaneous' trip of two or more reacter }.coolent pump ' bus circult treakers shs11' set exceed '1.3 seconds $. A W ~ $s W '@}.[:- ~ ia s R$ 'E.',.2*.2. '

  • ;;,;.4.a:M W.C7 &.

-. 9 4 / h }h -l.,, The'1.3 seconds detsy specified above is based ca a' 5AR assu:sption of.1,.6 seconds , j L

  • M elapsed time betvsen interruption of power to the 10P bus sad the st..t of red 2,1',.(-

insertion, minus e 0.3 seccad allovence for', the trip breaktr and the ECCA release. E-i . < <tyr.,.: m,.e. - i The allowable delay for the undervoltage relay is obtained by subtracting the l . [@*'7, i j stelsys. listed belov from 1.3 seconds., These delays ares I .c ylM 4%...

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n. %'s l n~ ;.. 1. An ellowsuce far the Ec? noter est doesy (0.25 seconds) k- .:;5@% yw .v s ,s j 2.J 14 tic delay (0.1 second) - 9.]. 1.' G i*v. 3!;!.1!ncertainty allovence (0.2 seconds). .y

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l .l. v. The ellevable relay delay is therefore: -. ~.<.I.. Si~J , ' ',. R, i 64; , j '. ? 1.6 F$AR totst delay e.. R breaker and Qreleilip ~~' g' b #'*

  • l [ ?/"..

M Design basis 1.3 N,. - k,,./[ *.'- -bei de'cey 7 '.';,.,, 0.25 s 0.1 14ste delay f:r.,.'Q '<,,." * -02 Uncert.einties ->g 4 O. n teley deley tLao g

  • n q,
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. s.m TT ?. The 0.73 sacer.d relay delay came is obtained by subtracting conservatively - I 4 f f 1erge ellovsnces from the T3AR total delay timeir 71 sat tasting could result Ilh. in e higher allevable relay delay time 1 it*can be,shown tha: the 1.6 ]Ql*{'t @ (#4P. F 4 ,../. second FSAR total deley time is still se ' 7.9 ' - @;'s *:'t J7] *

  • 4

~4 t ~~J sk. Sincerely, J t ~~ $ip!... R.E. She 144 as p. J p,. Northernservlee.Lehtoa I .i., II3 3 Ib ',* +@W: g.. #, " a.Q, g..

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f = N.- CDdT 94 3 i Pe=c h/Mame Tuhaniogy Gamp ~Qd y / wet 296 5374 n== unch 3,1994 satime: BM Clem2 Den be Pois Seash (I.O.75P343) { of ( he EEJICTEfMGCEANICAL DIVII!OM

2. R. W a mpaakar sa: 1 E. Salni:k B. E. Cox Sandy Lasukasvies d the MEwaikas ofEcs has nupassed soms mome dem tuh ntached healD. The foDowies mememkm b what we have rundDy availabla. If h6e *=dha==ia=

is nam'ad, plause let as hurw. Ecewer, tais is all we are able to pewride Brus of chafge. Any =hfier=mf m*-= sir = wlD regers : Av hans of M

  • tbne.

Plasse naas, an of me 20owag dan is *W anc meted. Base Power = 4476 kW Base Voltags - 2309 V Bass currea = 64dL! A Base Impaulanca = 3.574 ohne Per unit primary raamuses, si = 0.1063 Per unit saanday meansa, s = 0.0877 Per unie 3rimary runis. e M'c, r.e = OJoa51 Per anh sencedary asis. (runnlag), rm = 0.tKn9 Per unit smendary rests. OocksC, r = 0.0166 Per unft==- 2 masames, x, = 4.378 O Per imit soleissiast runessaca, z." = 0.167 Opna cirinit A.C. thns constantT"* = 1.861 sec. Skott c!riat A.C. sins constus T" = 0.0677 anc. Maasms oflaatia = 10,100 DHF Load tar 9e E synchannous speed (azid loop) = 31,400 fNbe Load areae a synshrneous sped one too,) = 23,200 twba Thare is ao curys syndabla May for Pt. Basch, het scres PCOQ30189A tbr Doli che Naan spars amener which is na elaarical Ant e==) can be need. A copy of enrve PCOC30389 A it is also anschad. [ =. P. C. fish.arean r".===resar/n&vne Twhnnkgy Aen.ahmana cauam.rr,_ 308 ' 3W d Ud >f0!n53H3 Ow2M Wobd Catai >5, G WWW Calc. No. 09334281-01 O Rev.1 Page A7 of A18 Project No. 09334-281

O wico i eiceriere-rc -g y 231 West Michigan Milwaukee, WI 53201 Fax Cover Sheet I DATE: June 19,1997 TIME: 9:00 PM f TO: Rick Higdon PHONE: (312) 269-8723 Sargent & Lundy FAX: (312)269-3757 FROM: John McDermid PHONE: (414) 221-2341 Wisconsin Electric FAX: (414)221-2010 Calc. No. 09334281-01 RE: Undervoltage Analytical Umit Calculation Information Rev.1 Page A8 of A18 CC: Project No. 09334-281 Number of pages including cover sheets: 107 + 5 cover pages This is transmission 1 of 5: pages 1-13 + cover Message U Per your fax June 19 1997 this transmission contains items referenced in calculation 95-0095. The following references are provided / superceded: 7.1 This is a general reference book. I don't think it contains infonnation necessary to prepare the calc 7.2 I am forwarding FSAR 14.1.8, FS AR Table 14 3, and Technical Specifications section 15.2.3 as the Accident Analysis Basis Document is not part of our Current Licensing Basis. 7.1 Forwarded 7.4 Forwarded 7.5 Forwarded 7.6 Unit 1 previously forwarded, Unit 2 forwarded in this transmission 7.7 Fluke data sheet with uncertainty is forwarded 7.8 Previously forwarded. This document is the ABB 27D relay instn.iction manual. 7.9 Please use the 5 TV 2 bulletin from your library unless it does not contain sufficient information 7.10 Unable to locate 7.11 Forwarded 7.12 Page listing PT shop order (S.O.) is forwarded 7.13 Historical Reactor Trip Time test data is tabulated as an attachment to calc 95-0095. Is the attachment missing, or do you need the origine' test data sheets? 7.14 NA 7.15 Forwarded: lix17 at end of transmission (4 ca) 7.16 Forwarded: 1lx17 at end of transmission (4 ca) 7.17 Section applicable to device uncertainty quantification is forwarded (pages 1 50) 7.18 Forwarded - (~] 7.19 Forwarded 'u 7.20 Forwarded 7.21 - New item. SR 90 test instrument is used in RMP 26 to time Reactor Trip Breaker opening.

Q Please note that a rigorous 'As Found' / 'As Left' drift analysis is not required for this calculation. PBNP is presently performing this type of analysis as part of an ongoing program to quantify instnament device and loop errors. Analysis of reactor trip breaker opening time can be performed to a 95/95% confidence level. (our preliminary estimates 1ndicate that this is equal to 94.16 mS) assuming that the time dats is normally distributed. Else, a value that bounds all historical data may be used (100 mS). My records indicate that the previous transmission should have included data from the Cl4 AMPS database on the 273 (4) / A01 (2) UV relays for both units, however this information is included with this fax. I will forward a calculation number on Monday. t O Calc. No. 09334281-01 Rev.1 'O-- Page A9 of A18 Project No. 09334-281 .__-____m__.

Cale. No. 09334281-01 Rev.1 Page A10 of A18 Project No.09334-281 s Summary Report or statistical Determination of Significant Reactor Trip Brer.ker Opening Time UNIT 1 UNIT 2 Breaker Test Date Cycles to mSee to Outt'ler? Breaker Test Date Cycles to mSee to Outlier? Trip Trip Trip Trip RTA-1 3/17,94 5.0 83 No RTA-2 11/3'84 4.5 75 No 4/22 85 5.0 83 No 10/26/85 4.0 67 No W22/86 5.0 83 No ~10/10/86 - 3.4 57 No 4/887 4.5 75 No 10/12.87 4.6 77 No 4 13!88 4.5 75 No 10/26/88 4.0 67 No Sr3'89 4.0 67 No No 4 13'90 3.6 60 No 11490 4.5 75 No 5/1/91 4.5 75 No 10/17.91 3.8 63 No 5/6e92 3.4 57 No 10/192 3.3 55 No 4/27/93 3.8 63 No No 4'14 94 4.2 70 No 10,11 94 3.6 60 No 4/1/95 4.0 67 No 10:31,95 3.8 63 No , O 4'8 96

t 35 xe to'32 96 t8 3o xo BYA-1 3!!7/84 4.5 75 No BYA1 11 84 3.8 63 No 4<22 85 4.2 70 No 10/26/85 4.0 67 No 4/22 86 4.0 67 No 10/10/86 4.0 67 No

) 4/8/87 4.0 67 No 10/12/87 3.6 60 No J 4/13'88 4.0 67 No 10 26/88 4.5 75 No Si3 <89 4.0 67 No No l U13 90 4.0 67 No 11:4/90 40 67 No fil:91 4.0 67 No 10/17.'91 3.8 63 No 5 6'92 3.0 50 Nu-10/1/92 4.0 67 No 4,27 93 3.8 63 No No 4'14 94 3.9 65 No 10:11,94 4.2 70 No 411'95 4.0 67 No 10/31<95 4.2 70 No 4 8/96 1.8 30 No 10/31/96 2.4 40 No RTB-1 31784 4.7 78 No RTB-1 11/3/84 3.7 62 No 4'22.85 4.0 67 No 10/26'85 4.0 67 No 4-22.86 4.0 67 No 10/10'86 3.4 57 No 4.8 87 4.2 70 No 10 12:87 3.6 60 No 4'13.88 4.5 75 No 10/26:88 3.4 57 No 5G89 3.7 62 No No 4/13 90 4.0 67 No 11/4.90 3.0 50 No Sil:91 4.0 67 No 10 17:91 4.4 73 No 5:6 '92 ~ 3.0 50 No 10'192 4.3 72 No h 4 27.93 3.9 65 No No 41494 4.2 "l0 No 10/11.94 4.0 67 No 4'1'95 3.4 57 No 10/31.95 4.0 67 No 4896 2.2 37 No 10/31:96 1.9 32 No i

t w a9 m ow m m p e r- - -.. n a we n n -- - - - _. _..w - co w w - I-l' (3 q BYB1 3'17/84 6.0 100 No BYB-1 11/3/84 - 4.4 73 No 4'22:85 5.0' 83 No 10/26/85 5.0 83 No 4'22/86 5.0 83 No-10/10/86 4.0 67 No ( 4 Si87 5.0 83 No' 10/12/87 4.2 70 No 4 13/88 5.0 83 No 10'26/88 4.2 70 No 5/3.89 4.2' '70 No No 4'13'90 5.0 83 No-11/4 90 4.0 67 No 5,1<91 4.5 75 No 10'17'91 4.6 77 No 5'6/92 4.4 -73 No 10/1/92 4.5 75 No 4/27/93 4.0 67 No No 4'14/94 39 65 No 10/11h4 3.6 60 No 4/1/95 4.4 73 No 10/31/95 3.8 63 No 4 8/96 2.2 37 No 10/31/96-2.0 33 No Cycles msec 1 Count 96 96 Mean ' 3.948 65.80 i St Dev 0.760 12.67 'O Outlier Criteria 3.192 3.192 95/95 Tot Mult 2.240 2.240

  1. of Outliers 0

0 95/95 Value 5.650 94.1.367 l Calc. No. 09334281-01 Rev.1 Page A11 of A18 Project No. 09334-281 .O - - - - - - _ _ - - - - - - - - - - - - - - - ~ ~ - - - - - - - - - - -

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t Calc. No. 09334281-01 Nuclear F Wastinghousa P S'A'4a'A18 p( Projeet No. 09334-281 Technica! Bulist,m O. 7" /=y m M S100 V An advisory notice of a recent technical development pertaining to the installation or operation of Westinghouse-supplied Nuclear Plant equipment. Recipients should evaluate the information and recommendation, and initlete action where appropriate. P.O. Box 355. Pittsburgh, PA 15230 t umoet' b Suoject y UNDERVOLTAGE TRIP PROTECTION NSD-TB. 92-03-RO Date REACTOR PROTECTION SYSTEM 05/15/92

  • I
  • ALL PLANTS WITH UNDERVOLTAGE PROTECTION 386 References Anects Safety Yes @ N fof 3 TECHNICAL SPECIFICATIONS Related Ecuioment No O B ACKGROUND INFORM ATION lt has been brought to the attention of Westinghouse that there may be confusion at some plants about the Reactor Trip System Response Time accounted for in the plant Safety Analyses and listed in the plant Technical Specifications for the Reactor Coolant Pump (RCP) Undervoltage Trip function. The confusion is a result of the interpretation of the definition of response time in the plant Technical Specifications, wording in some plant's Bases section of the plant Technical Specifications, and the unique accounting of channel response time in the Safety Analyses for the Complete Loss of Flow accident scenario which credits the Undervoltage Trip function.

The definition of Reactor Trip System Response Time in the Technical Specifications is: "The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage." Westinghouse analysis interprets loss of stationary gripper coil voltage to mean " rods are free to fall." Based on this definition of response time and the response time values listed in the Technical Specifications, plants typically write response time test procedures to test and verify that channels are in compliance with the Technical Specifications. The RCP Undervoltage Trip channel response time,like other channel response times in the Technical Specifications, is the same value as accounted for in the Safety Analyses crediting that channel. Typically, Safety Analyses response times includes hardware related time only. However, the response l h

  • y time accounted for in the Safety Analysis for the Complete Loss of Flow Accident is unique in that non-hardware related times are included in the total analyzed time. Included in the response time for the Complete Loss of Flow Safety Analysis is an allowance for the anticipated time it would take for the Addisonalinformauon. if Required, may be obtained from the Originator. Telephone A12 374 6457 or (WIN) 284-6457 ongrator Approval

? .1I !L..D @NL l T. P. Williams. Tech. Specification Operational Services L.. R. Benson 1 O l hj Domestic Customer Projects J. J. McinerS$1 T ch. S e. Operational Services Neither Westinghouse Electne Coroo,an or,ts employes mame any warranty or representanon wim respect to the accuracy. compieieness or usefulness of the information contained in this report or assume any responselity for liaDAry or damage which may resalt from the use of sucn informanon. NSD 2067 0 02'89 NIO 2057 A 02/89 h

I i NSD-TB-92-03-RO l A Qf Page 2 of 3 l Undervoltage Relay to detect a loss of voltage when there is an instantaneous loss of bus voltage. When the supply voltage to the Reactor Coolant Pumps is lost instantaneously, the potential exists for the RCP's, or other loads on the bus, to generate an Electro-Motive Force (EMF) back onto the j bus during coastdown. The effect of this back EMF is to cause the voltage across the bus to decay I at some finite rate instead of instantaneously. The Undervoltage Relay may not detect the instantaneous loss of voltage but may be influenced (held up) by the EMF being generated by the bus loads. This will cause a delay in the time it takes for the bus voltage to decay to a value below the Undervoltage Relay Trip setpoint (this is not to be confused with the intentional time delay set into the Undervoltage Relay actuation to prevent spurious trips due to momentary fluctuations in bus voltage). Based on the definition of response time in the Technical Specifications, the monitored parameter has exceeded its trip setpoint, but the channel sensor (Undervoltage Relay) is unable to detect this due to the back EMF. RECOMMENDED ACTION. The Safety Analysis assumes a total time response of either 1.2 or 1.5 seconds depending on the plant and analysis, and this is the time response that is listed in the plant Technical Specifications. g This time is comprised of several components. O a) The EMF delay irem the time of the loss of bus voltage until the EMF generated by the bus loads has decayed to a value less than the Undervoltage Trip setpoint. b) The inherent Undervoltage sensing circuitry time delay (including time for Measurement & Test Equipment) from the time the Undervoltage Trip setpoint is reached until an Undervoltage Reactor Trip signal is generated. This value is based on the manufacturer's specifications for all the components used in the Undervoltage circuitry. c) The intentional time delay set into.the Undervoltage Relay actuation to prevent spurious reactor trips from momentary electrical power transients. d) The time delay for the Reactw Trip Breaker to open and the RCCA grippers to release. ~" These values are added to obtain a total time response for the RCP Undervoltage Relay channels. Of these values, the EMF delay time (a) and the RCCA gripper release time component of (d) are l not determined during surveillance testing for Technical Specification Compliance of the channel time respcnse. Westinghouse assumes that the sites have accounted for the bus decay time for their particular. plant configuration and tk gripper release time of 150 ms when preparing the test procedure for g V the Undervoltage responte time. Westinghouse assumes an allowance for the bus decay time in Calc. No. 09334281-01 Rev.1 Page A15 of A18 Project No. 09334-281 i .-------- j

s,.. NSD-TB-92-03-RO Page 3 of 3 the analyses, but the actual bus decay time should be determined for each plant based on _ - knowledge of bus loads which would contribute to the decay time. Plant testing procedures typically require testing of the channel hardware only. Therefore,if the channel hardware is tested within the total Safety Analysis times minus the bus decay time, the total time accounted for will not exceed the Safety Analysis time. g Westinghouse recommends that plants review their procedures to-verify that bus decay time is applicable to their plant bus configuration and properly accounted for in plant test procedures. O. ) ) Calc. No. 09334281-01 ] Rev.1 Page A16 of A18

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Project No. 09334-281 9 e

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~ Se'ction 1 INTRODUCTION 1.1 GENERAL DATA ( For hot and/or cold performance, see Figures 5-1 and 5-2.) Electrical and mechanical design characteristics of the Reactor Coolant Pump V11001-Al are listed briow in Table 1-1. TABLE 1-1

SUMMARY

OF GENERAL DATA U Characteristics . '3 Model.................. V11001-Al Type................... Single-Stage, Centrifugal Head................... 252 feet Fl ow................... 90,000 gpm Impelle r................. Seven-vane, single-suction type Motor Brake Horsepower A Hot (specific gravity 0.745).. 4926 m* U Cold (specific gravity 1.006).. 6607

  • H" Speed................

1191 (Hot) 1188 (Cold) Ins ulation.............. Class B Vo l ta g e............... 4,000 Tolts Current Hot (specific gravity 0.745).. 621 Amps Cold (specific gravity 1.006).. 828 Amps Frequency.............. 60 cps g Phase................ 2 Phase rq Power Input i Hot (specific gravity 0.745).. 3962 KW- ~. - Cold (specific gravity 1.006).. 5280 KW Cooling Water Requirements Upper bsaring oil cooler.... 150 gpm at 1050F 0 Lower bearing oil cooler.... 5 gpm at 105 F Oil Capacities Upper oil pot. 175 gallor.s Lower oil pot.......... 25 gallons Calc. No. 09334281-01 Rev.1 Page A17 of A18 eS !v Project No. 09334-281 WMP. t1 bm

r . I LOUIS ALOS I 2,. 1 y s 8 \\.,-), 1 utton \\ .,..z :, p .v i ..,9 SPEED-TORC.UE CURVE FOR CEliTRIFUGAL PUMPS 'i '+h, USED FOR MOTOR DESIGli WiiEli ACTU AL I W^ ( 100

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-4 g.. l 0 + +-~ 8 6 00 ' '100 O J 20 40 ' 60 % OF FULL LOAD TORQUE Basis for motor design'using this curve:

1. 7'otal load inertia (including any couplings or gearing)

~.~ not to exceed: 'a. The MEMA value for the moto'r rated horsepower, for 1800 rpm & slover motors.

b. 25f. of the MEHA value, for 3600 rpm motors.

1

2. The 100d torque point on the curve corresponds to motor nameplate horsenower, and is therefore equal to motor rated torque.

mixed-flow, ,3. Curves shown are not' applicable to axial-flow, pisten, or scrou pumps of any kind. above load will i Noto: A motor designad' to safely accelerate the a load having a different speed-3 not necessarily be ablo to start even though tho differenco may appear clight. torquo curve, i I 9 /.ppr v d. by A l O.-. _/ (,# - / ^ .7f Curvo ! 18290

C&W 09334261-01 Rev.1 Page F2 ofF2 Prof. No. 09334-261 toc := 1.661 seconds (RCP motoropen circtMHme constant) E g := 2558.926181 voMs (RCP motorintemel voNage bebre postulated loss of voMage, Kne to neutral, kom Attachments)

1. Calculate RCP motorintemal v0 Mage at the end of the maximum aHowable transient voMage decay time (per Vll.F.1.dland Vill.F.1.c).

1 t o := 0.65I seconds (maximum eMowable transient voMage decay time) I Egt:=h-lE gl e E gr = 2995.051071 vo#s li. Create a graph of RCP motorintemal voMage dunng the first 1.5 seconds aRet the postulatedloss of voMage (per Vll.F.1.d.ii) n := 0.1440 t := n-( 1440 . l. i,:=h lE gl e E J 4500 4$00 g m. 4300 4200 l 4100 4000 x 3900 l \\ 3800 3700 \\ 3600 3500 3400 3300 \\ 3200 3100 E,300o N 3 m 2000 s 2700 2600 \\ 2500 2400 \\ 2300 y 2l00 2000 \\ I 1900 1800 n00 1600 1500 N l 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 1.1 1.2 1.3 1.4 1.5 1.6 l t,

l RHR Pumn D&i d = Thne CM~1=% Calculation 0933428101 Rev.1 l Page G2 of G2 l Proj. No. 09334-281 Imed Data: 1.191 Fulllead Speed (RPM) 23200.0 Fulllead Torque (Ib-ft) 8 70100.0 Inertia, WK l kJ 514ed Torque) .g; l T' ne to ; iR9_._ r,, ,l_ 2 Decelerstei Cumulative..: u .....~. Speed atP (Speed at ; f at Start of..: !!andTorpo j > lead Speed ) Begimming ?Endi ,... " Speed Interval ?, 1 Net b through

Thne to c

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(1) -

4(2)? -(3); (4) : (5) c

(6)J

'(7)' ' (8)

(9) 100.0 1191.0 1188.6 238 100.0 %

23200.0 -23200.00 -0.02 0.02 99.8 1188.6 1186.2 238 99.6 % 23116.5 -23116.48 -0.02 -0.05 99.6 I186.2 IIB 3.9 238 99.3 % 23033.0 -23032.% 0.02 0.07 99.4 II83.9 1181.5 238 98.9 % 22949.4 -22949.44 -0.02 -0.09 1181.5 !!79.1 238 98.6 % 22865.9 -22865.92 -0.02 0.12 99.2 99.0 1179.1 1176.7 238 98.2 % 22782.4 -22782.40 -0.02 -0.14 98.8 1176.7 1174 3 2.38 97.8 % 22680 3 -2268032 -0.02 -0.17 98.6 1174 3 1171.9 238 973 % 22578.2 -22578.24 0.02 0.19 98.4 1171.9 1169.6 238 %.9% 22476.2 -22476.16 -0.02 -0.21 98.2 1169.6 1167.2 238 96.4 % 22374.1 -22374.08 -0.02 034 98.0 1167.2 1164.8 238 96 0 % 22272.0 -22272.00 -0.02 0.26 97.8 1164.8 1162.4 238 95.7 % 22202.4 -22202.40 -0.02 0.29 97.6 1162.4 1160.0 238 95.4 % 22132.8 -22132.80 -0.02 031 97.4 1160.0 1157.7 238 95.1 % 22063.2 -22063.20 0.02 -934 97.2 1157.7 1155 3 238 94.8 % 21993.6 -21993.60 -0.02 036 97.0 11553 1152.9 2.38 94.5*4 21924.0 -21924.00 -0.02 038 96.8 1152.9 1150.5 238 94.0 % 218173 -21817.28 -0.02 -0.41 l l 96.6 1150.5 1148.1 238 93.6 % 21710.6 -21710.56 -0.02 0.43 96.4 1148.1 1145.7 238 93.1% 21603.8 21603 84 0.03 0.46 96.2 1145.7 1143.4 238 92.7 % 21497.1 -21497.12 -0.03 -0.49 %.0 1143.4 1141.0 238 92.2 % 21390.4 -21390.40 -0.03 0.51 95.8 1141.0 1138.6 238 91.9 % 21311.5 -21311.52 0.03 -0.54 95.6 1138.6 1136.2 238 91.5% 21232.6 -21232.64 0.03 0.56 95.4 1136.2 1133.8 238 91.2 % 21153.8 211$3.76 0.03 -0.59 95.2 !!33.8 1131.5 238 90.8 % 21074.9 -21074.88 0.03 -0.61 95.0 .I131.5 1129.1 238 90.5 % i 20996.0 120996.00 ' 0.03 -0.64 - 94.8 .I129.1L . I126.7 -238 . 90.2% -.20926.4 i -20926.40 . -0.03 ., 0.66.. 94.6 1126.7 1124 3 238 89.9 % 20856.8 -20856.80 -0.03 0.69 94 4 1124 3 1121.9 238 P9.6% 20787.2 -20787.20 -0.03 0.72 94.2 1121.9 II19.5 238 833 % 20717.6 -20717.60 -0.03 -0.74 94.0 1119.5 1107.6 11.91 89.0 % 20648.0 20648.00 0.13 0.87 93.0 1107.6 1095.7 11.91 86.5 % 20068.0 -20068.00 0.14 1.01 92.0 1095.7 10R3.8 11.91 84.5 % 19604.0 19604.00 -0.14 -1.15 91.0 1083.8 1071.9 11.91 83.0 % 19256.0 -19256.00 -0.14 -1.29 90.0 1071.9 Values in colurna (5) for even values ofload speed (such as 100.0%,99.0%,98.0%, ets..) are read from the load speed-torque curve (Reference XII.Y). Values in column (5) between even values of load speed (such as 99.8%,99.6%,99.4%, etc.) are interpolated.

  • RCP DECD.XL5 a

_ _ _ _ _ _ _ _ _ _ _ - _ _ _ -}}

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